ML19263D849
| ML19263D849 | |
| Person / Time | |
|---|---|
| Site: | Yellow Creek  |
| Issue date: | 03/27/1979 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML19263D850 | List: |
| References | |
| NUDOCS 7904130329 | |
| Download: ML19263D849 (3) | |
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UNITED STATES y7 NUCLEAR REGULATORY COMMisslON 3 j.I, I
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WASHINGTON, D. C. 20555 MAR 2 7 '979 Mr. J. E. Gilleland Tennessee Valley Authority 830 Power Building Chattanooga, Tennessee 37201
Dear Mr. G11:
aland:
Your letter to me dated Fehruary 23, 1979 was one of several letters that I recently received concerning Combustion Engineering, Inc. topical report,
" Qualification of Class IE Instrumentation" (CENPD-255). Your letter, as well as the others, expressed the concern that our review of this topical report would not be performed on a schedule compatible with Combustion Engineering's equipment qualification programs.
In response to your con-cern, I would like to discuss (1) our overall plan for reviewing the imple-mentation of Institute of Electrical and Electronics Engineers (IEEE) Stan-dard 323-1974, " Qualifying Class IE Equipment of Nuclear Power Generating Staticns" and (2) how we intend to proceed in our review of CENPD-255.
Recognizing that IEEE Standard 323-1974 represented a departure from the previous standard on equipment qualification, the staff develcped Task Action Plan A-24, " Qualification of Class IE Safety-Related Equipment" to handle the generic aspects of the implementation of this standard.
The purpose of this plan was to review and evaluate qualification methods, test plans, and test procedures for Class IE equipment presented in vendors' topical reports. The review of the topical reports was to be followed with an audit of qualification reports during the operating license review of each application.
Our progress to date on Task Action Plan A-24 nas been limited.
Topical reports have been received from three nuclear steam supply system vendors, Westinghouse, Combustion Engineering, and 3abcock & Wilcox. The Babcock &
Wilcox report was not received until just recently, February 1,1979.
The first topical report that we reviewed was WCAP-8587, " Methodology for Qualifying Westinghouse PWR-SD Provided NSSS Safety Related Equipment."
This report was reviewed first because the first operating license appli-cation that requires implementation of IEEE Standard 323-1974 employs a Westinghouse nuclear steam supply system. Our review of WCAP-8587 has lead us to conclude that we will not be able to write a generic evalua-tion of a gealification topical until we have reviewed detailed inferaation on the impleme,tation of the methodology on applications which reference WCA P-8587.
Therefore, for the first several plants that reference that topical report, we plan to review in detail the methods used to qualify 79003 0% q
A 2 7 379 Mr. J. E. Gilleland the equipment on a plant specific basis.
We expect that as a result of our plant specific reviews, we will require modifications to the topiCJI report. Ehen adequate information has been incorporated into WCAP-8587 as a result of these plant reviews, we will issue a safety evaluation.
In concert with the acceptance review of the CESSAR System 80 final design approval submittal, the staff has completed a preliminary review of CENPD-255.
The staff has found the discussion of qualification methodology to be much too general to support a detailed review.
This matter was discussed with Combustion Engineering in a meeting on the CESSAR System 80 design on February 12, 1979.
Subsequently, Combustion Engineering indicated that they are revising CENPD-255 and that a revision containing a portion of the information we require will be completed i, July 1979.
We expect that they will submit the revised report shortly F reafter. As i
soon as we receive the report and have determined that sufficient infor-mation has been provided for us to initiate our review we will develop a review schedule.
We will continue to keep you informed by sending you notices of meetings and meeting summaries dealing with this topical report.
I trust you will find this information useful.
Sincerely, p,
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Harold R. Ciaton, Director Office of Nuclear Reactor Regulation
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